05000280/LER-1988-041, :on 881016,engineering Evaluation Revealed That Existing Lifting Frames Installed Over RHR Pumps,Associated W/Piping & Electrical Supply Lines,Not Seismically Qualified.Caused by Inadequate Analysis

:on 881016,engineering Evaluation Revealed That Existing Lifting Frames Installed Over RHR Pumps,Associated W/Piping & Electrical Supply Lines,Not Seismically Qualified.Caused by Inadequate Analysis

ML18153B555
Person / Time
Site:	Surry
Issue date:	11/15/1988
From:	Benson D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
88-062, 88-62, LER-88-041, LER-88-41, NUDOCS 8811280072
Download: ML18153B555 (4)

LER-1988-041, on 881016,engineering Evaluation Revealed That Existing Lifting Frames Installed Over RHR Pumps,Associated W/Piping & Electrical Supply Lines,Not Seismically Qualified.Caused by Inadequate Analysis

Event date:
Report date:
2801988041R00 - NRC Website

text

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I NRC Form 361 19-831 POW 28-06-01 LICENSEE EVENT REPORT (LER)

U.S. NUCLEAR REGULATORY COMMISSION APPROVED 0MB NO. 3161M1104 EXPIRES: 8/31/88 Surry Power Station, Unit 1 &;

2 DOCKET NUMBER 121 PAGE 131 o Is I o I o I o 12 1 a I o 1 I OF n I ~

FACILITY NAME 111 TITLE 141 Lifting Frames Over RHR Pumps Not Seismically Qualified EVENT DATE 151 LER NUMBER (61 REPORT DATE 171 OTHER FACILITIES INVOLVED (BJ MONTH DAY YEAR FACI L.ITY NAMES DOCKET NUMBER ISi 1 I c 11 s a a a la - o I 411 -o Io i Ii 1 ls s Is OPERATING THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Chock on* or mar* of rha follovying) (111 MODE (91 N

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60.731*1121111 60.73(*11211111 60.73(*112111111 LICENSEE CONTACT FOR THIS LER (121 D. L. Benson Station Manaaer 60.73(*112JllvJ 73.71lbl 60.73(al(2llvl 73.71(*1 60.73(all211vlll OTHER (Spacify in Absrracr b*low *nd In T*xr, NRC Form 60.73(all2JlvlliJIAI 366A) 60.73(all211vlllllBI 60.7311112Jlxl TELEPHONE NUMBER AREA CODE 18. I O I 4 31 r; I 7 I - I ~ 11 I st I u COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (131 CAUSE SYSTEM COMPONENT I

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ABSTRACT (Limit to 1400 spac*s. I.*.* *PProxim*mly fifroan singls,spac* ryp*wrlmn lin*s) 1181 NRC Form 318 19-831 On October 16, 1988 with both Units 1 & 2 in Cold Shutdown (CSD),. and the Residual Heat Removal (RHR) system in operation, an engineering evaluation revealed that the existing lifting frames installed over the RHR pumps, associated piping, and electrical supply lines, were not seismically qualified.

The pumps were declared inoperable, and a* lOCF~S0.72, non-emergency report, was made to the NRC.

It is speculated that the lifting frames were installed as a temporary structure to facilitate maintenance and were never removed.

Hence, the appropriate engineering analysis and evaluations were not performed on the structures.

As an interim measure, the lifting frames were braced to ensure they would withstand seismic loads.

The lifting frames will be removed during the present unit outages and new frames will be designed and installed during future refueling outages.

Present maintenance and engineering practices preclude similar occurrences of placing structures over safety related equipment without adequate engineering reviews.

8811280072 881115 PDR ADOCK 05000280 S

PNU

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Nhc Farm 366A (9-83)

F.1!\\CIL_riv NAME (1)

LICENSEE E.. T REPORT (LER) TEXT CONTINUA..

DOCKET NUMBER (21 POW 28-06-01 U.S. NUCLEAR REGULATORY COMMISSIOII!

LER NUMBER (6)

APPROVED 0MB NO, 3150-0104 EXPIRES: 8/31 /88 PAGE (3)

Surry Power Station, Unit 1 & 2 0 1 s IO I O IO 12 i 810 Bl 8.- 0 I 4 I 1 -

01 0 0 I 2 OF O 13 TEXT (ff more spaca is n,quimd, use additiofllJI NRC Form 366A 'sJ (17)

NRC FORM 3HA (9-831 1.0 Description of the Event 2.0 3.0 On October 16, 1988 with both Units 1 & 2 in Cold Shutdown (CSD), and the Residual Heat Removal (RHR)

{EIIS-BP} system in operation, an engineering evaluation revealed that the existing lifting frames installed over the RHR pumps {EIIS-P}, associated piping, and electrical supply lines, were not seismically qualified.

A static.analysis of the frames determined that stresses in excess of the material yield point could exist under seismic loading.

Therefore, since a potential existed for failure of the lifting frames during a design basis earthquake, which could result in the inoperability of the RHR pumps, the pumps were declared inoperable, and a 10CFR50.72, non-emergency report, was made to the NRC.

Safety Conseguences and Implications The residual heat removal system is required.to bring the re*actor coolant system from conditioi:is' *of approximately 350 degrees Fahrenheit and 450 psig, to cold shutdown conditions.

Heat removal at greater temperatures is by the steam and power conversion system.

Procedures exist that instruct the operator on actions to take in the event residual heat removal capability is lost.

Therefore, the health and safety of the public were not affected.

Cause

Although it is not known when the lifting frames were installed, -it is speculated that they were installeq as a temporary structure to facilitate maintenance and were never removed.

Hence, the appropriate engineering analysis and evaluations were not performed on the structures.

4.0 Immediate Corrective Action(s)

As an interim measure, the lifting frames were braced to ensure they would withstand seismic loads.

5.0 Additional Corrective Action(s)

The lifting frames will be removed during the present unit outages.

New frames will be designed and install~d during future refueling outages.

• u.s. GPO, 1988-520-589100070

POW 28-06-01

~1------------------------------

N~C Form 366A

• a U.S. NUCLEAR REGULATORY COMMISSION

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• LICENSEE E T REPORT (LER) TEXT CONTINUA APPROVED 0MB NO. 3150--0104 EXPIRES: 8/31 /88 F"CILITY_NAME' (1)

DOCKET NUMBER (21 LER NUMBER 161 PAGE 131 YEAR

SEQUENTIAL -:,:*:*:*:: REVISION NUMBER

..... NUMBER Surry Power Station, Unit 1 ~ 2 0 I 5 I O I O I O I 2,s I O 81 8.. 0 I 4 11 -

0 ~ 0 I 3 OF O I 3 TEXT (ff more space is n,quimd, use additional NRC Fann 3118A :.J.1171 6.0 Action(s) Taken to Prevent Recurrence Pres~nt maintenance and engin~ering practices preclude simi~ar occurrences of placing structures over safety related equipment without adequate engineering reviews.

7.0

Similar Events

None.

8.0 Manufacturer/Model Number N/A NRC FORM 31111A (9-831

• u.s. GPO, 19BB-520-589t00070

-... *-.. ~,--

e VIRGINIA ELECTRIC ANO POWER COMPANY Surry Power Station November 14, 1988 U.S. Nuclear Regulatory Commission Document Control Desk 016 Phillips Building Washington, D.C.

20555 Gentlemen:

P.O. Box 3115 Surry, Virginia 23883

• Serial No.:

Docket No.:

Licensee No. :

88-062 50-280 50-281 DPR-32 DPR-37 Pursuant to Surry Power Station Technical* Specifications, Virginia Electric and Power Company hereby submits the following Licensee Event Report for Surry Units 1 and 2.

REPORT NUMBER 8~041-00 This report bas been reviewed by the Station Nuclear Safety and Operating C~ttee and will be reviewed by Safety Evaluation and Control.

Very truly yours, David L. Benson Station Manager Enclosure cc: Dr. J. Nelson Grace Regional Administ~ator Suite 2900 101 Marietta Street, RW Atlanta, Georgia 30323

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